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Abstract
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This study is thermodynamically analysis the Bushehr water-water
energetic reactor sub-channels of the reactor’s core fuel assemblies in Bushehr
Nuclear Power Plant, in the transient state, modified COBRA-EN code was
used for the failure of one of the cooling pumps. Among the channels in the
reactor’s core fuel assemblies that are used to cool the core, there is channel
that has a maximum power factor that is known as the hottest channel. It is
very important to thermodynamically investigate this channel to determine the
cooling features of the reactor’s core. Finally, the numerical modelling results
were compared to the reported safety results of Bushehr plant’s reactor in final
safety analysis reports.
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